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Pulstar Annual Rept, 780701-790630
	ML19254A785
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Site:	North Carolina State University
Issue date:	06/30/1979
From:	; North Carolina State University, RALEIGH, NC
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e PULSTAR ANNUAL REPORT TO UNITED STATES NUCLEAR REGULATORY COMMISSION for the Period of 1 July 1978 - 30 June 1979 Submitted by J. R. Bohannon, Jr.

Nuclear Operations Administrator NCSU GUCLEAR REACTCP 'ROGRAM Compiled by Thomas C. Bray PULSTAR Reactor Supervisor

Reference:

PULSTAR Technical Specifications Section 6.7.5 Docket No. SC-297 Department of Nuclear Engineering North Carolina State University Raleigh, North Carolina 27650 August 6, 1979 7 908370 382 bl 828 !,18

DEPARTMENT OF NUCLEAR ENGINEERING PULSTAR REACTOR ANNUAL REPORT For the Period: 1 July 1978 - 30 June 1979 The following report is submitted in accordance with Section 6.7.5 of the PflLSTAR Technical Specifications:

6.7.5.(a): Reactor Operatine Excerience (1) The NCSU PULSTAR reactor has been utilized for the following:

a. Teaching and Short Courses 110.76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months

b. Graduate Research 15.16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months

c. Isotope Production 503.84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months

d. Neutron Activation Analysis 1005.52 hours6.018519e-4 days 0.0144 hours 8.597884e-5 weeks 1.9786e-5 months

e. NPP P ctor Operator Training 947.73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months

f. PULSTAR Reactor Operator Training 25.02 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

g. Reactor Calibrations and Measurements 159.77 hours8.912037e-4 days 0.0214 hours 1.273148e-4 weeks 2.92985e-5 months

h. Reactor Health Physics Surveillance 18.63 hours7.291667e-4 days 0.0175 hours 1.041667e-4 weeks 2.39715e-5 months

i. Tours and Visitors 25.98 hours0.00113 days 0.0272 hours 1.62037e-4 weeks 3.7289e-5 months J. Faculty Research 29.72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Total Hours 2842.13+

Same reporting period 1977-1978 2623.30 A cross section of experir9ents performed relate to these areas:

a. Deeelopment of Prompt Gamma Facility in Beam Tube Nc. 2.

b. Ball Milling and other flow / tracer atudies.

c. Development of Neutron Radiography Unit in Beam Tube.

d. Reactor Noise Measurements Using Fuel assembly shaker and reactivit: oscillater in Beam Tube No. 1.

e. Physics Tests of 5 x 5 Reflected Core No. 3.

f. Absolute Flux measurements in the PULSTAR cree.

g. Neutron Activation for Analysis of Coal, Pe t roleu.. Products, Fly Ash, Animal Tissue and Rain /Ri.ver water.

h. NAA of Liquid Effluents from fuel fatricaticn plant.

This applied to total hours reactor cperating time devoted to the areas a-j. Multiple irradiation capability ("piggybacking") enables us to provide service to several different users simultaneously, hence the reactor utilization hours (* above) is higher by a factor of - 2.5 *han actual operating hours.

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'z) Design Changes Accomplished:

79-1 Installation and Routine Operation of the 5 x 5 Reflected Cort No. 3 --- Allows routine operation of the 5 x 5 Core reflected on two sides by graphite and eouipped with ratating vertical exposure ports.

79-2 Modification to Pneumatic Transfer System for Nitrogen Injection When Operating Reactor --- Provides for reduced '2 Argon production when reactor is operating at full power level.

79-4 Add Check Valves to Raw Water System to Prevent Possible Cross-Contamination --- a change made to assure separation of reactor service water system and domestic water supply as described in IE Circular #77-14.

79-5 Reposition Linear Power Channel Automatic Control Energize Switch --- Authorized adjustment of auto channel energize switch as a result of D.C. 79-1.

79-6 Modification to Fission Chamber Drive Support Tube --- Provided for proper channel overlap between source range and inter-mediate range power measuring channels as a result of D.C. 79-1.

79-7 Reposition Low Shutdown Margin Alarm Switch --- Made necessary by shift in physical position of fuel as described in D.C. 79-1.

(3) Changes in Performance Characteristics and Operating Procedures Related to Reactor Safety:

a. Addition of 5 graphite reflector assemb'ies to 5 x 5 Reflected Core #1 (D.C. 79-1) altered the nucl3ar characteristics of the reactor core in the following manner: increased negative moderator temperature coefficient, increased excess reactivity, reduced shutdown margin and lower radial peakiag factor which reduced the total peaking factor,

b. Procedure to allow adjustment of Lcg N Channel compensation voltage prior to reactor startup (Operations Manual change A C-lc'5 ) increased Log N/Startup Channel overlap by one decade.

(4) Results of Sur"eillance Tests and Inspections:

The reactor surveillance program has revealed no significant or unexpected trends in reactor systems performance during the past year.

All inspections conducted of reactor systems have yielded routine results with no singularities observed.

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6.7.5.(b): Tota! Eneref Outout.

742.83 MW-Hours (EFMH) 30.95 MW-Days (EFMH)

Pulse Operations:

O

Reacter was critical:

1176.06 Hours

Total Cumulative Energy Outnut Since Initial Criticality:

3922.91 MW-Hours 163.45 MW-Days 6.7.5.(c): Number of Emercency and Unscheduled Shutdowns :

One emergency shutdown was initiated on 11 August 1978 when the Regulating Rod drive switch did not return to the neutral "off" position after rod drive. Reactor was shut down by manual scram function. See 18 August 1978 report to NRC Region II office.

. Number of Inadvertant Scrams:

39 Reasons: (1) Cperator error 31 (2) Loss of campus power 2 (3) Linear Power Channel range switch 2 (4) Low Primary Flow setpoint drift 1 (5) Safety Flapper position switch 3 Explanation of (1) above:

Nuclear Power Plant Operator training (27)

NRP Staff operators (4)

Explanation of (2) above:

Loss of campus and hence building power normally results in a reactor shutdown.

Ex,lanation of (3) above:

The range selector switch on the Linear Level power measuring channel aad developed faulty contact make-and-break characteristics. Conventional switch contact cleaning cperation provided acrrection.

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Explanation of (4) above:

Primary coolant flow rate trip switch activated at a conservative 490 gpm rather than 475 gpm, the adjusted setpoint. Small indicated fluctuations of brief time duration are normal in the primary cooling system floa.

Explanation of (5) above:

Operator error. After having conducted reactor operator training involving routine flapper valve opening and closing, a licensed operator made a

" key-on" startup and upon reaching 150 kw in his approach to rated power, the reactor tripped (as per RSS design should the flapper be open).

Opere :or in training did not pull flapper-close handle with enough force to rroperly close the position switch. -

6.7.5.(u). Major Maintenance coerations None during this reporting period.

6. 7. 5. ( e ) - Chances in the Facility, Procedures, Tests and Experiments (1) Design Change 79-1, "5 x 5 Reflected Core No. 3, Installation and ,

Routine Operation" was proposed to extend reactor fuel lifetime, optimize burnup and included the usu of rotating vertical exposure ports designed to ' ore unifcrmly irradiate target material.

Safety evaluat on s 7 mary: "...the 5 x 5 Reflected Core No.

3 can be ooerated within the analytical envelope developed in the

?ULSTAR FSAR and the present Technical Specifications. Further it is concluded that there are no unreviewed safety questions pursuant to 10CFR 50.59, and therefore ; NRC approval required."

(2) Design Change 79-2, " Modification to Pneumatic Transfer System for Nitrogen Injection when Operating Reactor" was tethod utilized to reduce Argon-41 production and release in and from the PULSTAR reactor facility. Earlier attempta to reduce leakage air flow through P-N system, and hence curtail '2 Ar production, had not been effective.

Keeping system purged with ni trogen has proven to be the only reliable

- Ar reduction technique.

Safety evaluation summarf "This design change does not involve an unreviewed safety question since the nitrogen injection fitting (nozzle) will not affect the operation of the reactor or the RSS."

(3) Design Change 79-4, " Add Check Valves to FULSTAR Raw Water System to Prevent Possible Cross-contamination" was made in response to IE Circular 77-14 Two series check valves and a gate valve were installed in the raw (donestic) water supply line to the reactor facility to satisfy guidelines of the NRC Circular.

Safety evaluation sumnary concludes: "...thus installed, th-check valves addition does not constitute an unreviewed safety question since operation of the reactor will not be affected and there will be no impact on the Reactor Safety System."

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(4) Design Change 79-5, " Reposition Auto Control Channel Energize Switch for use with 5 x 5 Reflected Core #3" was necessary as a result of a new ganged control rods critical position for Core #3. 5x5 Reflected Core #1 auto energize switch position was 14.5" but Core

3 requires the switch be moved to 13.5" due to lower ganged rods critical position -- a result of Core #3's greater k-excess.

Safety evaluation summary concludes that operation of the 5 x 5 Reflected Core #3 with the ganged Heg Rod in automatic, at a position >l3.25', would c.ot adversely alter the flux distribution in regard to the safety analysis performed for allowing operation of tne 5 x 5 R.C. #3.

(5) Design Change 79-6, " Modification to Fission Chamber Drive Support Tube" was necessary for routine operation with the 5 x 5 Reflected Core #3 due to a shift in core flux produced by fuel repositioning and the relative proximity of the startup channel detector to the shifted fuel. The change raised the detector - two inches which yielded the desired initial count rate and enabled reactor startups with the fission chamber in the "0" position per standard cpcrating procedure.

Safety evaluaticn summary, "This change does not alter the operation of the Startup Channel or its RSS inhibit functions but provides for greater safety by increasing the amount of overlap between thc Startup and Log N channels."

(6) Design Change 79-7, " Reposition Low Shutdown Margin Alarm Microswitch for use with 5 x 5 Reflected Core 43" provided for repositioning the LSDM alarm microswitch at the control rods position corresponding to a 0.4% ak/k shutdown margin because of increased k-excess of new core.

Safety evaluation summary, ". . .in accordance with PULSTAR Final Safety Analysis Report, section 7.4.2., 'A microswitch is located at a pre-selected position on all control reds and if rods are not out beyond this position when the reactor power reaches 4 watts, a LSDM alarm is generated'."

(7) Procedure Change 3-78, " Emergency Plan for the NCSU PULSTAR Reactor".

Rewritten to conform to ANS 15 16, Standard for Emergency Planning fer Rasearch Reactors and to include experience corrections from past drills and raining.

No safety eva uation appropriate. Chai .g ' made to conforc.. to ANS standard.

(8) Procedure Change 4-78, " Revision to Calibration of Pool Level Measuring Channel procedure, PS-2-02-5:51". Made to add precautions to decrease likelihood of damaging bubbler hose and to tighten acceptance criteria of calibraticn.

Safety evaluation not required. Proposed revision is more conservative than current procedure with respect to safety.

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(9) Procedure Change 5-78, " Emergency Procedures for the NCSU PULSTAR Reactor". Rewritten to conform to ANS 15.16 Standard for Emergency Planning for Research Reactors.

No safety evaluation appropriate. Change made to conform to ANS standard.

(10) Procedure Change 6-78, " Revision No. 1 to Special Procedure 3.2, Fuel Handling Procedures. This change revised procedure format in conformance to SP2.1., added definitions, limitations, guidelines and precautions not detailed in original version of SP3.2.

Safety evaluation summary, " Original safety related procedural steps content has not been altered. This revision represents a more comprehensive version of the original.

fil) Procedure Change 1-79, " Revision of H. P.-20-9 and H. P.-20-lO".

The test instruments utilized to conduct these Health Physics procedures were replaced by improved equipment allowing increased accuracy in the measurement of pH and resistivity.

No safety evaluation appropriate.

(12) Procedure Change 2-79, "H. P.-20-14, Radiation and Contamination Survey of FULSTAR Bay" is a new formal procedure designed to comply with the requirements of 10 CFR 20.201. Technical Specificaticn 6.7.5.g. and 10 CFR 20.201 requirements for accomplishing said surveys were being met prior to the institution of HP-20-14 and resulting data was an. is being recorded and filed.

No safety evaluation is appropriate for this new procedure.

(13) Procedure Change 3-79, " Administrative Procedure 2.0, Procedure for Evaluating r A Reporting Defects and Non-compliance in Accordance with 10 CFJ '

. A new procedure addressing the issue of reporting possible sub3tantial safety hazards produced by the facility, a component within the 'acility or some activity of the facility.

Reporting procedures Are therein presented to the public as well as members of the staff.

No safety evaluation is appropriate for this nev administrative procedure.

(14) PULSTAR Project P-15, " Reactor Noise Experiment", describes a design to mechanically vibrate a fuel assembly in the reactor core and to measure the effect of the fuel movement on the measured reactor transfer function.

Safety evaluation summary:

(a) Peactivity worth of experiment proposed will be less than T.S. limiting value for moveable experiments.

(b) The experiment integrity will not be adversely affected by temperature change and there is no anticipated change in chemical composition or likelihood of radiolytic decomposition cf the experimental equipment.

(c) va terials selection for cor.struction of the vibrator device will be made to preclude chemical interatticn with reactor components.

(d) Activation of the fuel vibrating apparatus . . . will be minimized

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by separation from the core and at the proposed operating level of ~1 kw the radiation hazard to experimenting personnel will be minimal.

(15) PULSTAR Project P-16, " Preliminary Tests for Prompt Capture Gamma-Ray Research on the PULSTAR Reactor Tangential Sean Tube (No. 2)",

describes an experiment to determine the effect on the reactor core of collimator and shield placement in B.T. #2 and to measure neutron and gamma-rhy flux inside and outside the beam tube with and without target samples inserted near the core.

Safety evaluation summary:

(a) The reactivity effect of placing lead and graphite collimators near the core in beam tube #2 will be less than O.6% ak/k.

(b) The shielding and collimators in the beam tube will not be exposed to water and these materials can easily withstand the range of temperatures that exist in the beam tube.

(c) The lead and concrete collimators will be enclosed in aluminum or cadmium or will be painted with a sealer and samples intro-duced will be doubly encapsulated in plastic vials. Hence, interaction of physical or chemical nature will not occur between experimental and reactor componentc.

(di Radiation levels generated during the course of this experiment will not be sio nificant and will originate primarily from scattering or activation from target materiils inside the beam tube.

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6.7.5.(f): Radioactive Effluents Liquid Wastes (by Quarter)

1. Radioactivity Released During the Reporting Period (a) (b) (c) (d) (e) (Period)

No. Total Volume Diluent Tritium Batches Activity Released Volume Activity uCi/ml liters liters pCi 27 76.58 93,300 1.372E7 126.68 1 July - 30 Sept 1978 15 39.11 47,070 1.372E7 0.00 1 Oct - 31 Dec 1978 18 16.73 57,410 1.372E7 71.53 1 Jan - 31 March 1979 12 33.06 38,100 1.176E7 0.00 1 April - 30 June 1979 (f) 165.48 pCi total activity released (g) 198.21 uCi total Tritium activity released.

2. Identification of Fission and Activation Products The radioactive concentration in any batch released this past year did not exceed 4 E-5 uCi/ml. Therefore, fission and/or activation products were not identified.

3. Disposition of Liquid Effluents Not Released to the Sanitary Sewer System.

The concentration of radioactivity in each batch of liquid waste at this facility during the past year was less than 4 E-7 uCi/ml when the authorized daily dilution factor was considered.

Therefora, all batches could be and were released to the sanitary sewer system. This paragraph was not applicable during the year 1978-1979.

Gaseous Wastes

1. Radioactivity Discharged During the Reporting Period (in curies) for:

(a) Gases Period Time uCi/ml hrs. Ci 1978: 1 May - 17 Juj y 4.32E-8 1855.30 2.72 17 July - 21 Sept 5.63E-8 1583.18 3.03 21 Sept - 20 Oct 5.39E-8 696.75 1.26 20 Oct - 20 Nov 4.56E-8 175.42 1.20 20 Nov - 19 Dec 4.81E-8 707.00 1.16

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Period Time pCi/ml hrs. Ci 1979: 19 Dec - 15 Jan 2.01E-8 639.92 0.44 15 Jan - 14 Feb 4.03E-8 717.83 0.98 14 Feb - 19 Mar 2.90E-8 791.42 0.78 19 Mar - 17 Apr 1.85E-8 728.30 0.46 The following two (2) periods are eported so that the next " year" over uhich the gaseous effluent may average mcre nearly conforms to the annual reporting period:

1979: 17 Apr - 16 May 2.06E-8 795.62 0.56 16 May - 18 Jun 2.88E-8 779.92 0.76 (b) Neither the Constant Air Monitor in the Bay nor the Particulate Monitor in the exhauct atack evidenced any particulate released having a half life ir. excess of eight (8) days.

2. The gaseous activity released during this past year was A-41 in the amount of 12.05 Ci or 4.17E-8 uCi/ml averaged over 8495.12 Hrs.

A nitrogen purge of the experimen al facility the Pneumatic System (P-N) was installed in March, 1979, to redace the production of A-41. This purge is to be turned on during periods of reactor operation when the P-N System is not to be used. The effectiveness of this purging can be seen by comparing the periods.

1979: 19 Mar - 17 Apr 1.85E-8 728.30 0.46 17 Apr - 16 May 2.06E-8 795.62 0.56 16 May - 18 Jun 2.88E-8 779.92 0.76 with the other periods during the past year.

The MPC for A-41 in an unrestricted area is 4E-8 pCi/ml .

Solid Waste

1. Total Volume of solid waste -- 35 ft. .

2. Total Activity -- 0.007667 curies

3. Date3 of shipme cs and disposition:

11 July 1978 Burial by Chem-Nuclear 15 September 1978 Burial by Chem-Nuclear 17 October 1978 Burial by Chen-Nuclear 22 November 1978 Sr-ial by Chen-Nuclear 20 December 1978 Burial by Chem-Nuclear -

6 February 1979 27 June :.979 Buria_

Burial by by Chem-Nuclear Chen-Nuclear

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6.7.5.(g): Personnel Radiation Exposure Report (Reporting Period - 1 June 1978 - 31 May 1979)

Name Total dose (rem)

Staff Bilyj, Stephen J. O.222 Bohannon, Jr. , James R. O.098 Brackin, Thomas L. 0.077 Bray, Thomas C. O.177 Cross, Robert D. 0.098 Douglas, William G. O.130 Dunn, William L. O.103 Eudy, Lucille P. O.119 Gant, D. Michael O.150 Gurkin, Louis M. (6/1/78-11/30/78) 0.067 Lewis, Luther E. 0.019 Miller, Garry D. O.158 Price, Leslie F. (5/1/79-5/31/79) 0.013 Rhiner, Glenda D. 0.0 Thorsen, Leigh A. (6/1/78-9/30/78) 0.025 Weuver, Jack N. 0.036 Faculty Elleman, Thomas S. O.130 Gardner , Robin P. 0.080 Kohl, Jerome 0.119 Murray, Raymond L. O.392 Saxe, Raymond F. 0.056 Stam, Ephraim 0.088 Verghese, Kuruvilla 0.066 Zumwalt, Lloyd R. 0.072 Radiation Protection Office Personnel Ball, Arthur C. 0.056 Caruthers, L. Thomas 0.0 Clark, Samuel T. (6/1/78-2/28/79) 0.012 Corbett, E. Marcell e 0.038 Debnam, Joshua 0.014 Freeman, Ralph M. 0.012 Grady, Stanley M. O.148 Howard, auzanne M. 0.0 Mangum, Royelle O. O.123 Morgan D. William 0.0 custadians Dunn, Johnnie J. 0.040 Jones, Arthur 0.037 Sanders, Joseph 0.051 021 '.28 Students 79 film badges were issued to Nuclear Engineering Department students during the reporting period. No significant radiation exposures were reported. The majority of the radiation exposures were in the 'no measurable exposure' range.

iisitors and Short Courses 804 film badges were issued to visitors and participants in shsrt courses during the reporting period. No significant radiation exposures were reported. The majority of the radiation exposures were in the 'no measurable exposure' range.

The shield for the Neutron Radiography Unit (NRU) has been improved with each iteration. Thus, the radiation levels in the PULSTAR Bay have been significantly reduced. Routine work can be undertaken in the Bay with only normal precautions applicable to any Radiation Area. Plans are being formulated to further refine and improve tne NRU shield.

Summary of Radiatien and Contamination Surveys Routine contamination surveys in the Bay by the RPO have not disclosed any contaminated spots. Special contamination surveys made upon completion of RWP's have found evidence of unsuccessful clear -up af ter the work under the RWP. These spots were subsequently cleaned. This surveillance has maintained a clean Bay working area.

The Radiation and Contamination Surveys, giving due consideraticn to the influence of the NRU shielding, do not show any indication of change of radiation levels in the Bay.

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6.7.5.(h) Part 1 ENVIROMCv"AL RADIATION SURVEILLANCE REPORT AND ANALYSIS PROCEDURES APRIL 1, 1978 TO SEFIEMBER 30, 1978 Arthur C. Ball, Environmental Health Physicist Joshua Debna:n, Environ:nental Chemist Radiation Protection Council L. T. Caruthers, Radiation Protection Officer D. 'J. Morgan, Associate Radiation Protection Officer North Carolina State University Raleigh, North Carolina p

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1. INTRODUCTION The Environmental Radiation Surveillance (ERS) program at North Carolina State University has been in operation on a limited basis since August 1970 and as a funded program since July 1973. During these first five years as a funded operation, the program has grown to maturity. Local analyses now in-clude gross alpha and beta ev'nting of air, water, soil, vegetation, and sewage. Gamma analysis is performed on air, water, soil, vegetation, and milk. Strontium-90 analysis is perfor=ed on rater, milk, sewage, and waste water.

In order to perform the large and still growing number of analyses, the ERS staff of two full time persons and one part time student assistant utilize a well equipped laboratory. In addition to chemicals and chemistry apparatus, the laboratory includes a Beckman Widebeca II Lew Background Alpha and Beta Counter and a Nuclear Data ND-100, 4096 Channel Ga=ma Analyzer used with a Ge(Li) Detector and NaI(T1) Compton Suppression Unit on one half of the memory, and a 4" x 4" NaI(TI) Detector Crystal with a 1" x 2" Well on the second half.

The Ge(Li) system, having high resolution (but low efficiency), is used to identify specific radionuclides in air, water, vegetation, and soil sa=ples.

Counting timer are necessarily long as activities are low.

The NaI Well Crystal is used for detection of specific radionuclides where identification is known and higher efficiency is required. Iodine-131 detection in air and milk samples is the primary function of this system.

Camma spectra from samples counted on both detectors are stored on magnetic tape and analyzed on the IEM-370 Model 165 computer at the Triangle Universities Computer Center (TUCC). NaI(TI) spectra are first examined on the Cathode Ray Tube (CRT) on the ND-100 by means of overlaying a background spectrum of shnilar counting time. Any photopeaks observed are then analyzed by means of the Gauss analysis program. Ge(Li) spectra are analyzed for all ga=ma photopeaks by mear.s of the MONSTR Program which was =ade available by Oak Ridge National Laboratories in late 1975.

Calculations for specific activities for all sa=ples are acce=plished on a Wang Model 462 Progra=mable Electronic Calculator.

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2. AIR MONITORING Airborne particles are collected with high volume samplers equipped with 6" x 9" glass fiber filters and millipore pumps equipped with 47 mm millipore filters and activated charcoal cartridges.

These samplers are located in five sampling stations on the NCSU campus (see Table 2.1) and operate for six hours a day, Monday through Friday of each week. Samplers are turned on and off by a seven-day clock switch with actual time of run recorded on an electric timer which is switched on and off sisiul-taneously with the samplers.

After a ten-day decay period to eliminate naturally occurring radon and thoron daughters, the 6" x 9" glass fiber filters are combined for a composite sa=ple and analyzed with the Ge(Li) Detector and ND-100 Ga=ma Analyzer. The spectra are then put on magn (tic tape and ga:na activity is determined by use of the MONSTR Program on IUCC IDI 370 Computer.

The millipore filters are counted for 100 minutes each for gross alpha and beta activity (also af ter a ten-day decay period) with the Widebeta II.

The charcoal cartridges are analyzed ic=ediately as a composite sa=ple fer halogen activity by means of a long count (over the weekend following Friday collection) on the 4" x 4" NaI(T1) Crystal and ND-100 Ga=ma Analyzer.

A emination of halogen activity in gaseous form is accomplished by means of the overlay feature of the CRT on the NT-100. The sample spectrum is displayed simultaneously with a background spectre; of similar counting time. Ga=ma peaks above background which are observed in the sample spectrum may then be measured to determine specific activity by =eans of the computer program " GAUSS" and the IUCC Computer. To date, no gaseous halogen has been detected in air samples. Iodine activity which has been reported following at=ospheric nuclear detonations in the Peoples Republic of China has been nessured on the glass fiber filters indicating that the halogen has attached itself to dust particles and is no icnger in gaseous form.

Grcss alpha and beta activity is calculated from the Widebeta II printout and reported as Specific Activity in femto Curies per Cubic Meter (SA fCi/M ).

SA = ,} : "[C+3+.0025(C-3) where C = Sa=ple counts per 100 min 3 = Background counts per 100 min U = (.222 (100 m (fCi)

( *( * ""7) m..- 77}o For a sample collection time of 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months at a flew rate of 30 liters per minute:

3

- 1. 8 Volume = ( 30 )(30 hrs)(60 min /hr)( 1000 liters ) = 54 M Efficiency = .278 for alpha in the millipore configuration

.380 for beta in the millipore configuration therefore, U = 3.33 for alpha 4.56 for beta This problem is solved on the Wang Calculator with proJram " Gross a and E : 1e" Verification No. 234 or "SA Beta Air" Verification No. 309. -

Specific Activity for gamma emitters is calculated from the computer printout for the spectrum and is also reported as Specific Activity in fCi/M . The fission products reported as present in air sa=ples do not normally appear in background spectra; thus, it is not necessary to substract background peaks frem semple peaks.

SA = y/sec (

f ) ( V) ^ y .0025 3.7 x 10 5 y where y/sec is taken frem the MONSTR printout or converted from the area of the peak as determined frem the GAUSS printout I = Intensity (or abundance) of the gz=ma V = Volume of sample T

g = Half-life of nuclide in days c = Standard deviation of counts per see taken from MONSTR S

printout or converted to deci=al from GAUSS printout.

This problem is solved on the Wang Calculator with program ( Specific Activity" Verification No. 413.

During the period of this report, airborne activity has generally been declining following the last atmospheric test at the Lop Nor test site in March 1978. Typical lung hazard fission products are reported in Table 2.3 and other fission products associated with the Chinese testing are reported in Table 2.4. Gross beta activity is reported in Table 2.2. No significant alpha activity has been detected.

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h. n[i Table 2.1 Air Particle Sacpling Locations Designation Direction Distance Elevation Broughton Southwest 410 ft. - 55 ft.

David Clark Lab (DCL) West Library Northwest 629 ft. + 36 ft.

Riddick Southeast 325 ft. - 46 ft.

Withers Northeast 270 ft. - 19 ft.

1 Direction - Direction from Reactor Stack 2

Distance - Distance from Reactor Stack 3

Elevation Elevation with respect to top of Reactor Stack Table 2.2 AirborneGrossBetaActivity(fCi/M? 1C)

Date Broughton DCL Library Riddick Withers 1978 4/3-4/7 264.6 15.7 233.4 = 14.1 130.1 2 9.1 221.3 13.5 219.8 2 13.5 4/10-4/14 334.5 = 19.1 307.9 17.8 280.9 16.4 315.8 18.1 330.5 18.9 4/17-4/21 59.6 5.7 48.6 5.2 36.3 4.7 57.6 = 5.6 45.1 5.1 4/24-4/28 170.5 = 11.0 166.6 10.8 145.7 = 9.8 181.3 = 11.5 27.0 = 4.4 5/1-5/5 142.4 9.6 125.5 8.8 81.3 6.7 149.9 9.9 132.2 = 9.1 5/8-5/12 108.6

7.9 107.5

7.8 103.5 = 7.7 90.8 = 7.1 118.5 : 8.4 5/15-5/19 44.6 2 4.9 46.7 1 5.2 27.3 4.2 52.7

5.3 49.5 5.2 5/22-5/26 120.7 : 8.6 130.5 9.0 118.9 : 8.5 89.9 = 7.1 156.3 10.3 5/29-6/2 129.2

8.9 101.9 : 7.6 118.7 : 8.4 3.7 3.3 97.8 : 7.4 6/5-6/9 78.7 6.7 65.7 6.1 63.5 5.9 79.6 6.7 82.6 2 6.8 6/12-6/16 165.9 10.8 151.9 = 10.1 127.9 : 8.9 160.0 = 10.7 146.1 : 9.8 6/19-6/23 163.9 10.7 152.9

10.21 138.9

9.5 146.6

9.9 175.2 11.3 6/26-6/30 148.8 : 9.9 111.8

8.2 108.1 8.0 113.8 : 8.3 101.5 : 7.7 7/3-7/7 83.7 : 6.8 85.5 6.9 72.3 = 6.3 73.8 6.3 Not Operational 7/10-7/14 117.6 : 8.4 108.4

7.9 104.2 : 7.7 103.1 : 7.7 90.5 = 7.1 7/17-7/21 146.8 9.9 129.0 8.9 123.5 : 8.7 130.5 2 9.1 141.9 9.6 7/24-7/28 49.2 5.1 44.6 2 4.9 35.4 : 4.5 42.9 : 4.8 43.3 : 4.9 7/31-8/4 64.6 : 5.8 Si.7 = 5.5 52.5 5.2 66.4 5.8 62.9 : 5.7 S/7-8/11 48.6 5.3 53.t 5.6 38.9 4.9 44.4 2 5.1 41.5

4.9 8/14-8/18 60.0 1 5.7 54.7 5.4 48.1 5.1 54.1 = 5.4 61.5 = 5.7 8/21-8/25 96.3 : 7.4 104.4 7.7 80.2 6.6 105.3 2 7.8 90.3 : 7.1 8/28-9/1 48.6 = 5.1 49.5 = 5.1 42.2 = 4.8 44.6 : 4.9 61.3 = 5.7 9/4-9/8 65.9 5.9 85.9 2 6.8 80.4 i 6.6 88.1 = 6.9 E6.4 = 6.8 9/11-9/15 95.0 9.3 91.4 = 9.1 88.1 8.9 92.1

9.1 109.4 9.9 9/18-9/22 80.2

8.4 75.2 i 8.2 69.8 = 7.9 63.3 7.7 92.8 9.0 9/25-9/29 96.4 : 9.1 78.1 2 8.3 70.1 7.9 91.7 8.9 80.2 8.4 n'7 ? T, d C C ;) s 4

Table 2.3 Airborne Pereiculate Specific Activity ( y emitters)

(Ca= pus Average t?i/M iic) 144 141 103 106 952 , 95 Date 1978 Ce Ce Ru Ru 3 4/3-4/7 64.3

3.7 5.5 = 0.5 8.6 0.6 11.9 = 1.4 6.8 = 0.8 13.1 = 0.8 4/10-4/14 79.4

4.4 8.2 = 0.7 14. 7 = 0. 7 14.3 A 3.1 9.2 1.0 16.2 = 1.0 4/17-4/21 15.2 1.6 0.96 = .3 < 0.5 < 5.0 < 1.0 4.6 = 0.5 4/24-4/28 55.8 = 3.2 < 1.0 1.7 0.3 14.6 2.4 4.3 = 0.7 9.6 0.7 5/1-5/5 46.5 2.9 1.6 0.4 1.5 0.3 13.8 2.7 4.4 0.7 8.7 0.6 5/8-5/12 32.3

2.7 < 1.0 < 0.5 < 5.0 3.3

0.9 11.5 i 1.2 5/15-5/19 12.4 1.6 < 1.0 < 0.5 < 5.0 2.0

0.6 < 0.5 5/22-5/26 47.6

3.0 < 1.0 < 0.5 6.3 = 1.5 < 1.0 7.2 = 0.6 5/29-6/2 42.4 i 2.8 < 1.0 < 0.5 8.4

2.0 3.7

1.0 6.5 i 0.6 6/5-6/9 24.6 = 2.1 < 1.0 < 0.5 9.5

2.9 2.7 i 0.6 5.4

0.6 6/12-o/16 49.8 = 3.0 < 1.0 < 0.5 < 5.0 3.1

0.6 6.9 0.6 6/19-6/23 61.9 i 3.6 < 1.0 < 0.5 14.5 2.8 2.9 0.6 6.9 0.6 6/26-6/30 31.4 2.4 < 1.0 < 0.5 < 5.0 < 1.0 1.4 0.5 7/3-7/7 25.4

2.0 < 1.0 < 0.5 < 5.0 0.8 = 0. 3 3.3

0.5 7/10-7/14 30.6

2.4 < 1.0 < 0.5 10.9 = 2.9 1.4 i 0.5 3.5 = 0.6 7.17-7/21 36.3 = 2.6 < 1.0 < 0.5 12.5 = 2.9 < 1.0 3.8 = 0.6 7/24-7/28 11.7 = 1.7 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 11.5 = 1.8 < 5,0 < 1.0 < 0.5 7/31-8/4 < 1.0 < 0.5 8/7-8/11 7.3

1.7 < 1.0 < 0.5 . < 5.0 < 1.0 < 0,!

8/14-8/18 9.2 2.2 < 1.0 < 0.5 < 5.0 < 1.0 1.2 = 0.6 8/21-8/25 26.8 2.4 < 1.0 < 0.5 < 5.0 < 1.0 2.6 = 0.7 8/28-9/1 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 9/4-9/8 12.9

1.7 < 1.0 < 0.5 < 5.0 < 1.0 1.7 = 0.7 9/11-9/15 13.6 i 1.6 < 1.0 < 0.5 < 5.0 < 1.0 1.4 = 0.6 9/18-9/22 5.9 1.5 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 9/25-9/29 8.5 = 1.7 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 Table 2.4 Other Fission Products Detected in Air Samples (fCi/M =1c)

Isotope 4/3 - 4/7 4/10-4/14 4/17 - 4/21 I 6.1 = 0.7 < 1.0 < 1.0 Cs 8.0 = 0.6 9.6 = 0.7 1.4 = 0.4 Ba 7.6 = 0.8 13.9 1.8 < 1.0 La 8.3 2.5 11.6 i 3.6 < 1.0 n;7 c L .) /T"s3

3. MILK Milk is collected from the NCSU Dairy on a monthly basis. Samples are ana'.yzed for Strontium-90 actictity according to the procedures in Appendix A.

Milk is also analyzed for Iodine-131 activity as follows:

500 ml of milk is put into a 1000 mi beaker. 20 gm of Dovex 1-X8,

?Cf. 400 mesh anion exchange resin is added and the sample is stirred ott a magnetic stirrer for thirty minutes. The resin is allowed to m tle, transfe-red to a 20 mi vial and counted for gama activity in the well of the 4" x 4" NaI(TI) Crystal for 99,000 sec. The spectrum is then examined on the ND-100 CRT display and compared to a background spectrum with the use of the overlap feature of the ND-100. If an Iodine peak were observed, it would be evaluated with the use of the GAUSS Program and the TUCC Computer.

To date no Iodine-131 has been detected in the milk from tha NCSU Dairy.

This may be attributed to the f act that the cattle producing this milk are primarily silage fed, and therefore. would not generally ingest substantial quantities of the short lived nuclide Iodine-131 (half-life = 8.041 days) .

Tests conducted on spiked samples of milk have shavn the Iodine ; recedure to be approximately 957. efficient and the NaI(TI) Crystal nas a 31". efficiency for the 364.5 kev ga:::ma emitted by Iodine-131 la a sample counted in the well of the crys;al. The intensity (or abundance) of the 364.5 Kev ga=ma is i)27.

giving a 40", total efficiency for this procedure.

Table 3.1 Milk Specific Activity (pCi/1 i 1 )

131 90_ I Date or 5.19 0.61 < 2.0 4/53 4.26 0.54 < 2.0

'i'78 3.37 0.47 < 2.0 6/78 5.37 i 0.49 < 2.0 7/78 3.1.4 m 0.48 < 2.0 8/78 3.7.9 m 0.70 < 2.0 9/73 8

-e- [ 3 '36

4. SURFACE WATER Surface water is collected from Rocky Branch Creek at two locations:

ON - where the creek flows onto FOSU campus and 0FF = where the creek flows off of NCSU campus. Samples are collected in five-gallon Nalg2ne containers.

(These containers hold 19 liters when filled to the top.) Care is taken when filling the containers to avoid floating debris and bottom sediment.

Surface water is analyzed for gross alpha and beta activity according to the procedures in Appendix B and for gamma activity according to the procedures in Appendix C. Following gamma analysis, the condensed 18-liter sa=ple is diluted to 500 ml and analyzed for Strontium-90 activity according to procedures in Appendix A.

Specific Activities for surface water samples are reported in Table 4.1, No unusually high readings of Strontium-90 were noted during this reporting period; hence, the hypothesis of c delay in fallout frem atmospheric nuclear tests being washed into Rocky Branch Creek remains unverified at this time.

Table 4.1 Surface Water Specific Activity (pCi/1 1c)

Date Location

Cs Co Co K Sr Gross Beta April ON < 0.1 < 0.2 < 0.2 17.98 = 24.01 0.26 = 0.02 6.G1 = 0.49 1978 0FF < 0.1 < 0.2 < 0.2 8.89 = 23.97 0.51 0.04 8.08 = 0.59 May ON < 0.1 < 0.2 < 0.2 6.13 26.31 0.51 = 0.04 5.49 = 0.45 1978 0FF 0.68 = 0.55 < 0.2 < 0.2 < 2.0 0.75 i 0.05 5.90 = 0.47 June ON 1.35 0.33 < 0.2 < 0.2 < 2.0 0.21 i 0.02 3.55 = 0.36 1978 0FF 1.49 0.37 < 0.2 < 0.2 14.97 = 27.85 0.35 = 0.03 3.67 0.37 July ON < 0.1 < 0.2 < 0.2 < 2.0 0.37 0.03 3.23 = 0.37 1978 0FF < 0.1 < 0.2 < 0.2 23.70 = 22.32 0.29 = 0.03 6.18 = 0.50 Aug ON < 0.1 < 0.2 < 0.2 < 2.0 0.64 = 0.04 5.40 = 0.46 1978 0FF 0.10 = 0.42 < 0.2 < 0.2 < 2.0 0.59 = 0.04 5.78 = 0.48 Sept CN < 0.1 < 0.2 < 0.2 < 2.0 0.50 = 0.04 3.91 = 0.38 1978 0FF < 0.1 < 0.2 < 0.2 < 2.0 0.52 = 0.04 3.86 = 0.38

0N - Denotes Rocky Branch Creek as it enters NCSU ca= pus OFF - Denotes Rocky Branch Creek as it leaves NCSU ca= pus n'

U 'l

'7f

5. SOIL Soil samples are collected in January and July of each year. Surface samples are taken at four sites on or near ca= pus and deep samples (4.5 feet below surface) are taken outside of the radioactive materials burial ground.

An additional deep sample was taken thia reporting period in the vicinity of the West sample for comparison purposes.

The locations of the four surface samples are: North - near Bell Tower; South - between Morrill Drive and Western Blvd.; East - next to Rocky Branch Creek as it flows off of NCSU campus; West - next to Rocky Branch Creek as it flows onto NCSU ca= pus.

Soil samples are screened to remove rocks and vegetation matter, then ashed in a muffle furnace at 520 C for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . Approximately 0.1 gram from each sample is transferred to an aluminws planchet and counted for gross alpha and beta activity and approximately 50 grams are transferred to a plastic dish and analyzed on the Ge(Li) Crystal for gamma activity.

Following 100 minute counts each for alphs and beta activity, gross specific activities are calculated as follows:

SA =

{ hdC+B+.0025(C-B) where C = Sample counts per 100 min B = Background counts per 100 min U = (Efficiency)(Mass)(222 dis /100 min )

pCi Efficiency = .278 for a

.380 for 3 This pr oblem is solved on the Wang Calculator with program " Gross a or S = 1 : "

Verification Nc 234.

Soil s .etes to be scanned for ga=ma activity are weighed in small plastic dishes, placed in the Compton Suppression '! ell above the Ge(Li) Detector, and counted for 100,000 seconds each. The spectra are transferred to magnetic tape and sent to TUCC for analysis by the MONSTR progra= on the TUCC Ccmputer.

Specific Activity for ga=ma esitters is calculated from the computer print-out for the spectrum and is reported in Table 5.1 in piceCuries per gram.

The gz=ma energies from nuclides normally found in soil samples do occur in background spectra and are long-lived so they do not require decay time correction.

a :' O

o

^

.)

SA =

} h af oC +#

B

+* ( ~

}

where C = Ys per see from sa=ple spectrum B = Ys per see from background spectrum U = (.037 ,

- " )(Intensity)(Mass)

C C " Sample error from printout e = Background error from printout B

Thf s problem is solved on the Wang Calculator with program "Sp Act Y vith Ekg" Verification No. 359.

Table 5.1 Soil Specific Activity (pCi/gm 1c)

Location

Gross 2 Gross S Th Ra Cs K North 4.86:0.98 9.72:2.08 0.707 0.487 0.650:0.408 1.078:0.197 < 0.4 South 4.05:0.90 17.31*2.39 0.303:0.466 0.804:0.378 4.007:0.286 < 0.4 East 6.48:1.12 34.2623.15 1.53010.462 1.556=0.377 0.872:0.177 34.811=8.561 West 4.05:0.90 21.10 2.60 1.231:0.454 1.105:0.362 0.141:0.161 9.032:8.233 W(4.5') 1.9420.66 13.6322.21 OBG(4.5') 3.06:0.84 _15.39:2.47 NEG(4.5') 5.2001.06 28.06:3.01

Location - Denotes direction from reactor Burial Ground samples are in near proximity to fence ITEG denotes New Burial Ground OBG denotes Old Burial Ground (not presently in use) 4.5' denotes depth of sample; others are at surface

{\O b9

6. VEGETATION Edible crops (corn and soy beans) are collected frem the NCSU Farm at harvest tbne and analyzed for gross alpha and beta activity and specific gansa esitters. Pine needles and grass sa=ples are collected in January and July and are also analyzed for gross alpha and beta and specific gamma activities.

During this reporting period, only one pine needle sample and one grass sample were taken. These were in the vicinity of the South soil sample.

Specific Activities are reported in Table 6.1.

Procedures for preparation and analysis of vegetation samples are reported in Appendix D.

Table 6.1 Vegetation Specific Activity (pCi/gm

i c )

Sample Gross a Gross S Cs K Pine 0.064 .014 4.784 : 0.258 < 0.02 5.17 i 1.73 Grass 0.058 : .021 9.686 0.525 < 0.03 10.70 = 4.32 0 4 ', k b t . e

7. REACTOR WASTE TANKS AND SEWAGE Reactor waste tank monitoring has never been considered a part of Environ-mental Radiation Surveillance (ERS); houever, gross alpha and beta determina-tions have been carried out by Radiation Survey Technicians prior to release of tank contents into the Raleigh sewage system. The ERS personnel have developed a procedure for the determination of Strontium.90 in vaste tank water and the specific activities determined are reported in Table 7.1 along with the gross alpha and beta activities for the same samples.

Sewage water from the Raleigh treatment plant is being analyzed for gresa alpha and beta and Strontics-90 activity as an addition to the ERS program.

These specific activities are reported in Table 7.1 along with the reactor waste tank specific activities.

Procedures for gross alpha and beta analysir of sewage water and Strontium-53 analysis of both sewage water and waste tank water are in Appendices E and F r'.spectively.

Table 7.1 Waste Tan; nd Sewage Specific Activity (pC1/1 2 1 c)

Sample Gross a Gross S Sr WT #1 June < 0.5 587.1 30.6 1.23 = 0.25 WT 42 June < 0.5 667.9 = 34.6 1.38 : 0.26 WT #2 July < 0.5 332.0 = 18.6 0.77 = 0.22 WT 43 July < 0.5 332.6

19.6 0.88 = 0.23 WT #2 Aug < 0. 5 65.2 2 5.6 0.96 = 0.22 WT 03 Aug < 0.5 < 5.0 0.45 0.21 WT 41 Sept < 0. 5 57.9 = 5.2 1.44 = 0.25 WT 43 Sept < 0.5 39.4 = 4.5 2.40 x 0.29 May Sewage < 0.1 10.45 0.88 1.16 = 0.45 July Sewage < 0.1 10.48 = 1.33 1.73 = 0.58 Sept Sewage < 0.1 15.44 = 1.47 1.69 = 0.65

8. THERM 0 LUMINESCENT DOSIMITERS (TLDs)

TLD packages of two LiF chips and one CaSO :Dy dosimeter are located at 4

the five air sampling stations on the NCSU campus and at six reactor moni-toring stations. A control package is also kept in Room 214 David Clark Laboratories away from ionizing radiation sources. Locations of all TLD stations are indicated in Table 8.1.

LiF TLDs are exchanged monthly and read locally for exposure. CaSO 4 TLDs are also exchanged monthly and sent to Teledyne Isotopes for analysis.

Transit dosimeters accompany those shipped to Teledyne so that exposure accumulated during transit may be subtracted from exposure received on station.

Abnor= ally high readings for the locally analyzed dosimeters located on the West Wall of the PULSTAR Reactor Bay for August and September may be attributed to open beamport work conducted during those months. Low readings for corresponding contracted dosimeters are unexplained.

TLD exposure is reported in Table 8.2 as average weekly exposure (mR/wk).

~

mR/wk = ( D )7 where E = 2xposure Reading for TLD T = Transit Reading (if applicable)

D = Time on Station for TLD (in days) 7 = days in week This problem is solved on the Wang Calculator with program "TLD Weekly Avg" Verification No. 184.

O.,

, :) ,4u)

Table 8.1 Thermoluminescent Dosimeter (TLD) Locations Desismation Location Broughton 410 ft. southwest of and 55 ft. below top of Reactor Stack DCL Roof of David Clark Laboratories Library 629 ft. northwest of and 36 f t. above top of Reactor Stack Riddick 325 ft, southeast of and 46 ft, below top of Reactor Stack Withers 270 ft. northeast of and 19 ft. below top of Reactor Stack Control Room 214 David Clark Laboratories R-3 Entrance to NCSUR-3 Reactor Bay from Control Room PULSTAR PULSTAR Reactor Bay, West Wall Equipment Room PULSTAR Equipment Room East c,f PULSTAR Bay Control Room PULSTAR Control Room Pool Over FULSTAR Reactor Pool Stach Top of PULSTAR Reactor Stack Table 8.2 Thermoluminescent Dosimeter Readings (Average mR/wk based on Co-60 Standard)

Area Monitors

4 78 5 78 6-78 7-78 8 78 9-78 Broughton L 2.3 2.6 2.3 1.9 1.9 1.9 Broughton C 2.7 1.3 1.9 X 0.3 2.9 DCL L 1.6 1.9 1.1 1.3 1.3 1.3 DCL C 2.0 1.0 1.1 X 0.5 2.1 Library L 2.6 2.7 2.1 2.2 2.1 2.2 Library C 1.8 1.4 1.7 X 0.8 2.3 Riddick L 2.9 2.7 2.3 2.2 2.2 2.1 Riddick C 2.5 1.6 2.0 X 0.2 3.2 Withers L 1.9 2.3 1.9 1.8 1.6 1.9 Withers C 1.6 1.1 1.7 X 0 2.8 Control L 2.5 2.0 2.5 1.8 1.4 1.8 Control C 2.0 1.3 1.4 X 1.6 1.9 Reactor Monitors R-3 L 5.1 5.4 4.7 4.7 4.2 4.4 R-3 C 3.6 2.2 3.2 X 1.4 4.1 PULSTAR L 26.4 35.0 86.3 129.0 299.1 150.2 PULSTAR C 13.7 12.7 14.1 X 21.3 15.4 Equipment Room L 25.4 29.1 22.0 21.0 25.6 23.1 Equipment Roem C 19.4 13.8 17.2 X 18.8 17.5 Control Room L 6.4 7.3 9.4 10.4 23.5 13.0 Control Room C 4.4 3.5 3.9 X 3.5 4.7 Pool L 36.2 41.0 38.4 42.5 71.9 51.8 Pool C 26.2 22.6 24.3 X 28.7 26.3 Stack L 3.8 3.0 2.1 1.8 2.6 2.6 Stack C 2.0 1.3 1.5 x 0.7 2.5

L Denotes Locally Evaluated LiF Desimeters

C Denotes CaSO :Dy 4 Dosimeters Contracted to Teledyne Isotopes for analysis X Teledyne reports that Contracted dosi=eter readings for July were lost during a company relocation O/b

APPENDIX A Sr PROCEDURE FOR MILK AND WATER Phase 1

1. Put 500 mi milk into 1000 ml beaker, or dilute water sample to 500 m1 in 1000 mi beaker.

2. Add 30 gm Dovex 50W-X8 200-400 mesh resin and stir for one (1) minute on magnetic stirrer.

3. Adjust pH to 6.0 with pH Meter using 6 M NaOH while stirring. Continue stirring for 30 minutes after pH adjustment. (D0 NOT ADJUST pH OF WATER SAMPLES.)

4. Allow resin to settle, then aspirate milk or water from above resin and discard.

5. Add 200 ml distilled water (washing beaker sides) and stir.

6. Allow resin to settle again; then aspirate milk-water from above resin and diser.rd. Repeat washing if necessary to re=ove milk solid particles.

7. Add 200 ml 8N HNO an s n magnet c schrer for 30 dnutu.

3

8. Filter resin-acid mixture through Whatman-42 (or equivalent) filter paper in Buchner funnel.

9. Wash beaker with 50 ml 8N HNO and continue M1tering. Repeat was W g Wo 3

more times allowing each wach to filter completely. Discard resin. Save filtrate.

10. Add the 350 mi solution to a 500 m1 beaker containing several glass beads and evaporate to dryness.

11. Add 50 ml 307. H 220 and evaporate to dryness.

12. Add 20 ml 8N dNO 3 "" *"#E **** * #7"* " '

13. Add 20 ml 307. H 220 and evaporate to dryness.

14. Add 10 ml 0.08 N hcl and wam.

15 Add to 125 mi separatory funnel containing 20 ml 207. HDEHP,

16. Rinse beaker with 5 ml 0.08 N hcl and add to separatory funnel.

17. Repeat Step 16 and shake for two (2) minutes.

13. Allow phases to separate and drain off bottom aqueous layer into clean 100 mi beaker.

19. Add 20 n1 of fresh 207. HDEHP to second clean separatory funnel.

20. Add contents of beaker to second separatory funnel. Shake for two (2) minutes and allow to settle.

21. Drain off bottom aqueous layer into 20 mi vial for storage. Record time and date as T .

i 5

', 4 Ut

[i [{

Sr Procedure for Milk and Water, Continued Phase II (after at least 14-day ingrowth period)

1. Pour sample into 125 mi separatory funnel containing 20 ml 207. HDEHP.

2. Rinse vial with one or two ml 0.08N hcl and add to separatory funnel.

Shake for two (2) minutes and allow to settle.

3. Drain off bottom aqueous phase into its 20 mi vial. Record time and date as T2 '

4. Add 20 ml 0.08N hcl and shake for two (2) minutes. Drain off bottom aqueous phase and discard.

5. Add 20 ml 8N HNO and shake for two (2) minutes. Drsin off bottom aqueous 3

phase into clean 100 m1 beaker.

6. Repeat Step 5. (Add to same beaker.)

7. Evaporate contents of beaker to a few ml.

8. Transfer solution to flamed and cooled 2" planchet.

9. Wash beaker with a few ml 8N HNO and add to planchet. Continue washing 3

until beaker is clean.

10. Evaporate solution in planchet to dryness under infrared lamp.

11. Courc planchet in low background beta counter for 100 minutes and record midpoint of counting lime as T .

3 Milk samples are normally processed in pairs of spiked and unspiked one-half liter samples from each collection. Yttrium-90 ingrowth which occurs between T7 and T, becomes important only when T -T y is substantially dif-2 ferent between spiked and unspiked samples. Percent of 4.ngrowth (9 ) may be found by solving the equation = 1 - 2" Sr s This equatioa is solved on the Wang Calculator with program " Y Ingrcwth" Verification No. 207. If

]s ked is less than .99 or greater than'1.01, =ultiply this fraction by the actual spike added for use in O

calculating Sr Specific Activity. Specific Activity = 1 : (PicoCuries per liter) is calculated as follows:

~

-T/64 SA = C' - C (11b )2 5

where C = Counts per 100 min (unspiked sample)

C' = Counts per 100 min (spiked sample)

B = Counts per 100 min (Background)

Sp = Quantity of Sr spike in picoCuries (corrected for ingrowth if necesst y)

T = (T 3 ~

2 *E

~

3 2)unspk W hourO b )

90 Sr Procedure for Milk and Water, Continued B(C' - C) + C(C' - B) + C'(C - B)

(C' - 0)

This problem (Specific Activity with Standard Deviation) is solved on the Wang Calculator with program ,,90 5 S Milk" Verification No. 609.

Specific Activity for water is determined as follows:

SA = #m C + B + .0025(C - B)

} 2 where C = Counts per 100 min (sample)

B = Counts per 100 min (background)

T=T 3

~

2

" "#8) s U = (18 liters)(222 pCs 00 min ) (E) (I)

E = .265 = Total efficiency for water procedure I = Ingrowth percentage as explained earlier

= .974 after 14 days; .980 after 15 days, etc.

therefore, 1031 < U < 1059 (depending on ingrowth time).

Specific Activity for water is solved on the Wang Calculator with program "Sp.

Act, with Decay Sr" Verification No. 397.

9 APPEND 1X B GROSS ALPHA AND BETA DETERMINATION IN WATER

1. Transfer c. (1) liter of water to a 1000 ml or 1500 m1 beaker and evaporate to approximately 50 ml on hot plate in hood.

2. Traasfer sample to 100 mi beaker using distilled water and rubber policeman as necessary to insure complete transfer. (See Note.)

3. Evaporate sample to less than 10 ml.

4. Transfer sample to fla=ed and cooled 2" stainless steel planchet using distilled water and rubber policeman as necessary to insure complete transfer. (See Note.)

5. Evaporatc sample to dryness under heat lamp.

6. Count sample for alpha and beta activity for 100 minutes each in icw background alpha and beta counter.

Note: 6N ENO 3 may be used if necessary to insure quantitative transfer of sample.

Calculations:

Specific Activity (SA) pCi/1.

SA =

{ ifhC+B+.0025(C-B) where C = Sa=ple counts per 100 min B = Background counts per 100 uin U = (222)(Volume)(Efficiency)

= (222 disintegrations /100 min /pC1)(1 liter)(E)

E = .287 for beta, .210 for alpha U = 15.93 for beta, 11.655 for alpha This problem is solved on the '4ang Calculator with program " Gross a or b : 1r" Verification No. 234 0 '; /j7 OL ) ./1 /

APPENDIX C GAMMA ISOTOPIC ANALYSIS OF SURFACE WATER

1. Transfer approximately three (3) liters of 18-liter water sample into five liter boiling flask and boil at reduced pressure. (.7 atmosphere vacuum 1.m maintained in evaporation system to reduce boiling temperature and decrease possibility of velatilizing dissolved solids.)

2. As volume in boiling flask is decreased, periodically add water from 18-liter sample and continue boiling until entire sample has been reduced to approximately 200 ml. (As sample approaches final volume, reduce flame to prevent evaporation to dryness and reduce iossibility of breaking flask.)

3. Transfer sample to 400 m1 beaker rinsing flask several times with distilled water to insure quantitative transfer.

4 Evaporata sa=ple on hot plate in hood to approximately 25 ml.

5. Transfer sample to 50 ml covered plastic dish rinsing beaker with distilled water as necessary to insure complete transfer.

6. Place dish containing sample in Compton Suppression Well of GeLi Detector system and count ga=ma activity for 100,000 seconds.

7. Analyze ga=ma spectra for Specific Activity using MONSTR Program on the TUCC Computer.

Specific Activity for gamma emitters is calculated in picoCuries per liter as follows:

^" * * . 025(C - B)

.03 IV C B IV(.03 pCisec )

where C = Y/sec from 153 Printout for sample B = Y/sec frem IHM Printout for background r

C"

E * *## # * "#*# * ##* # " "

C B = Background error converted from Printout I = Intensity (or abundance) of g1=ma V = Volume of sample = 18 liters This problem is solved on the Wang Calculator with program "Sp Act y with Skg" Verification No. 359.

If peak does not appeer in 3kg Spectrum, 0 =ay be entered for 3 and r

3 b ) ib

APPENDIX D PREPARATION AND ANALYSIS OF VECETATION SAMPLES

1. Weigh out 100 gm of sam,le in drying dish and heat in drying oven for one day at 100 C.

2. Weigh and record weight of ceramic crucible, then transfer sample to crucible for ashing.

Note: Grass and Pine Needle sa=ples should be pulverized in blender before ashing to reduce volume so they will fit in crucible.

3. Ash sample in muffle furnace for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months at 520 C.

4. Weigh crucible with ashed sample in it to determine reduction factor (R)

R=

net wt after ashing

5. Weigh approximately 100 mg of sample in 2" aluminu= planchet and count in Widebeta II for alpha and beta activity for 100 minutes each.

Calculations for gross alpha or beta apecific Activity (SA)

~

SA =

m h C + B + .0025(( - B) where: C = 3 ample counts per u00 min B = 3ackground counts per 100 min

~

U = (Efficiency)(Mass)(R)(

8

")

This problem is solved on the Wang Celculator with program " Gross a or S = 1 "

Verification No. 234.

The remainder of the ashed sample is transferred to a plastic dish and analyzed for ga==a activity in the Compton Suppression Well of the Ge(Li)

Detect?r for 100,000 seconds. The spectrum is then put on magnetic tape and sent to TLICC for anal.ysis on the TUCC Computer with the MONSTR program.

Specific gar::ma activity is determined from the ecmputer printout with the same calculations and Wang Program as is used for soil sample:. using mass of sample times reduction facter in place of mass.

0 '( 5 k

APPENDIX E ANALYSIS OF SEWAGE WATER FOR GROSS ALPHA AND BETA ACTIVIN

1. Place 250 m1 sewage water in 400 m1 beak, tnd evaporate in hood to a few ti.

2. Transfer evaporated sewage water to 2" stainless steel pla..chet using 8N HNO 3 to wash beaker and 2nsure all of sample is transferred.

3. Evaporate sewage water to dryness on planchet under infrared lamp.

4. Count evaporated sample for gross alpha and beta activity in Widebeta II for 100 minutes each.

Specific Activity (SA) calcalation:

SA = = C + B + .0025 (C - B)

}

where C = Sample counts /100 min B = Background counts /100 min U = 222 VE = 222(.25)(Efficiency)

Efficiency = .278 for beta, .210 for alpha in this configuration U = 15.93 for beta, 11.655 for alpha This problem is solved on the Wang Calculator with program " Gross a or 5 = 1 c "

Verification No. 234.

0 0 <'G C :_ J 'sU

APPENDIX F STRONTIUM-90 ANALYSIS OF WASTE TANK AND SEWAGE WATER

1. Dissolve sample by placing planchet in approximately 200 ml of 8N HNO 3

in 250 ml or 400 ml beaker.

2. Heat to boiling on hot plate in hood and remove planchet with hemostat, washing planchet and hemostat jaws with 8N HNO 3

'9"**** * **

3. Add a few glass beids to beaker to prevent bumping and evaporate sa=ple to dryness.

4. Add 50 ml 307. H 220 and evaporate to dryness.

5. Add 20 ml 8N HNO 3 and evap rate t d m ess.

6. Add 20 ml 307. H 220 and evaporate to dryness.

7. Add 10 ml 0.08N, hcl and warm solution to insure sample is dissolved.

8. Transfer solution to 125 m1 separatory funnel containing 20 ml 207. HDEEP.

9. Shake sample for two minutes and allow phases to eaparate.

10. Drain off bottom aqueous phase into 20 mi vial. Note: Ingrowth period for Yttrium-90 is not required in this procedure since strontium and yttrium have not been separated until this point and are considered to be in equilibrium. The aqueous phase is saved only as a precaution and tests have shown that subsequent extraction of Yttrium-90 after an in-growth period (See Milk Strontium-90 Procedure) produces the same results; hc aver, efficiency is lower if ingrowth and extraction is used rather n direct extraction.

(Total efficiency = .265 with resin and ingrowth.

Total efficiency = .332 with direct extraction.)

11. Add 20 ml 0.08_N hcl and shake for two minutes.

12. Allow phases to separate, drain off bottem aqueous phase and discard.

13. Add 20 ml 8N HNO and shake for two minutes.

3

14. Allow phases to separate and drain off bottem aqueous phase into 100 mi beaker.

15. Repeat Steps 1; and 14. (Add to same beaker.-

16. Evaporate acid solution to a few ml on hotplate in fume hood.

17. Transfer sample to fla=ed and cooled 2" stainless steel planenet using SN HNO 3 fr m squeeze bottle to wash beaker and insure complete transfer.

1C

(,j ., adi$ >J}

Strontium-90 Analysis of Waste Tank and Sewage Water, Continued

18. Evapwate sample to dryness under infrared lamp.

19. Count sample for Yttriu:n-90 beta activity for 100 minutes in Widebeta II.

90 Sr Specific Activity (SA) calculations:

T/T SA = CU- B 2 gT/T,]C+B+.0025(C-B)

U 3

where C = Samp)e counts per 100 minutes B = Background counts per 100 minutes T = Decay time from extraction to midpoint of count T = Half-life of Yttrd"m-90 = 64 hours7.407407e-4 days 0.0178 hours 1.058201e-4 weeks 2.4352e-5 months U= (222 00 min )(Volume)(Efficiency)

U = (222)(.25)(.332) = 18.426 for 250 mi sample U = (222)(1)( 332) = 73.704 for one liter sample TM, problem is solved on the Wang Calculator with program "Sp. Act. with Decay

U Sr" Verification No. 397.

n '? ? 7 i' ')

Q !_ ; ) au

6.7.5.(h) Part 2 ENVIRONMEITIAL RADIATION SURVEILLANCE REPORT FOR THE PERIOD OCTOBER 1, 1978 TO MARCH 31, 1979 Arthur C. Ball, Environmental Health Physicist Joshua Debncm, Eavironmental Chemist Radiation Protection Council L. T. Caruthers, Radiation .:rctection Officer D. W. Morgan, Acsociato Radiation Protection Officer Ucrth Carolina State Univoroity Raleigh, North Carolina b b !b

1

1. INTRODUCTION Environmentr.1 radioactivity in the vicinity of North Carolina State University has been markedly low throughout the current reporting period. No increases have been detected subsequent to low level releases reported by nuclear power plants in other states or from any other sources.

Contracted analysis has been performed on Themoluminescent Dosimeters but not on other samples. This analysis provides the only readings for the TLD stations for January ed February 1979 as the reader used for local evaluation was not opera tonal.

2. AIR HONITORING No significant alpha or hr. logen activity was detected in any air samples taken during this reporting period. Gross beta activity is reported in Table 2.2 and specific activities for gamma emitters is reported in Table 2.3.

3. MILK No iodine activity was detected in any milk samples analyzed during this period. Strontium-90 activity is reported in Table 3.1. The reading for December is higher than nor=al, but is still well within safety limits. No attributabic cause is known for the abnormal December reading.

4. SURFACE WATER Gross alpha and beta and Strontium-90 activities are reported in Table 4.1 along with gamma esitters Cesium-137 and Potassium-40 (which were detected in only a few of the twelve samples reported).

5. SOI'.

Gross alpha and beta and specific gacen emitter activities are reported

~

for the various soil samples in Table 5.1.

6. VEGETATION Specific activities for corn, soy beans, and pine needles are reported in Table 6.1.

7. RLiCTOR WASTE TAIES AND SEWAGE Grous alpha and beta activities for the FULSTAR reactor waste tanks and for Raleigh seunge water are reported in Tobic 7.1. Strontium-90 activity is also reported for the sewage samp'.es.

8. THERM 0 LUMINESCENT DOSIMETERS ('"LDs)

TLD average ucekly exposure rec 4l go are reported in Table 8.2. Local

- evaluations were not performed d6 ring January and February of 1979 due to the non-operational status of the TLD reader. Repairs have now been eceptoced and local evaluation of TLDn resemed in March 1979.

n , a) 7r J J 4,4

()._'

Table 2.1 Air Particle Samplin8 Locations Designation Direction Distance Elevation Broughton Southwest 410 ft. - 55 ft.

David Clark Lab (DCL) West Library Northwest 629 ft. + 36 ft.

Riddick Southeast 325 ft. 46 ft.

Withers Northeast 270 ft. - 19 ft.

Direction . Direction from Reactor Stack Distance . Distance from Reactor Stock Elevation - Elevation with respect to top of Reactor Stack Table 2.2 Airborne Croco Beta Activity (fCi/M3*1o)

Date Broughton DCL Library Riddick Withers 1978 10/2-10/6 69.1 i 6.1 59.2 5.6 49.3

5.2 50.7

5.2 66.4 i 5.9 10/9-10/13 42.3 4.9 39.'/ c 4.8 43.7 = 5.0 52.2 = 5.3 33.1 4.5 10/16-10/20 46.5

5.0 41.0

4.8 42.8

4.9 39.7

4.7 40.1 = 4.7 10/23-10/27 42.1 4.3 45.4 5.0 41.7

4.3 40.1 4.7 39.7

4.7 10/30-11/3 60.3 5.7 62.5 5.8 55.5 = 5.4 56.3 5.5 58.3 5.6 11/6-11/10 74.6

6.3 87.9 6.9 53.3 = 5.3 66.9 i 5.9 76.0 = 6.4 11/13-11/17 43.6 4.0 40.1 4.7 46.3 5.0 10.1 3.4 67.3 5.9 11/20-11/24 77.9 i 6.5 55.9 i 5.5 60.4

6.1 63.4 i 5.0 93.3 2 7.3 11/27-12/1 34.9 6 4.4 33.8

4.3 21.3

3.4 29.4

4.1 30.7 = 4.2 12/4-12/3 29.8 4.2 34.6 4.2 23.7 4.1 19.5 3.7 35.7 A 4.4 12/11-12/15 19.0 i 3.6 34.9

4.3 37.3

4.4 33.8 = 4.5 47.1

4.9 12/18-12/22 31.1

4.4 46.5

5.1 37.1 = 4.7 76.8 6.5 35.1

4.6 12/25-12/29 70.1 i 6.2 83.7 i 6.8 81.1

6.7 66.4

6.0 75.6 = 6.3 1979 1/1-1/5 45.4 5.0 44.3 6 4.9 42.5 4.8 43.4

4.9 42.3 i 4.0 1/8-1/12 46.3 i 4.0 60.5

5.5 51.0 i 5.1 47.4 4.9 56.6 i 5.3 1/15-1/19 47.0 5.1 54.6 5.2 40.9

5.1 52.4

5.3 53.0

5.3 1/22-1/26 27.6

4.1 23.5

3.9 29.0 i 4.2 40.4 4.6 38.6 4.6 1/29-2/2 25.7 6 4.1 39.7 i 4.7 37.5 4.6 36.0

4.5 31.8

4.3 2/5-2/9 30.5

4.2 50.2 5.1 43.9 4.8 41.4 4.7 46.2 5.0 2/12-2/16 67.5

5.9 65.3 5.9 50.9

5.2 27.9

4.1 53.7 5.3 2/19-2/23 10.7

3.4 20.1

4.2 39.3 i 4.6 32.9 i 4.4 36.2

4.5 2/26-3/2 11.0 o 3.5 20.2

3.0 32.7

4.4 29.3 = 4.2 32.9

4.4 3/5-3/9 10.2

3.7 49.3 a 5.0 39.'/

4.6 44.3

4.8 46.3 i 4.9 3/12-3/16 13.0 3.7 52.4

5.2 45.0 i 4.9 26.1

4.0 41.9 : 4.7 3/19-3/23 23.6 t 4.6 32.9 4.4 34.2

4.5 21.9 i 4.0 32.9

4.4 3/26-3/30 55.5

5.4 59.4 i 5.6 50.2 i 5.2 41.0

4.7 45.4

4.9 n-n / E E.

Ci) *dd

3 Table 2.3 Airborne Particulate Specific Activity (Y Ecritters)

(Campus Average fCi/113 i i c)

Date ce 141 ce 103 Ru

Ru 5

Zr nib 1978 10/2-10/6 6.8

1.4 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 10/9-10/13 8.3

1.6 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 10/16-10/20 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 10/23-10/27 6.5

1.7 0.9

0.3 < 0.5 < 5.0 < 1.0 < 0.5 10/30-11/3 5.1

1.4 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 11/6-11/10 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 11/13-11/17 13.6

3.3 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 11/20-11/24 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 11/27-12/1 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 12/4-12/8 9.0 2.4 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 12/11-12/15 7.9

2.2 < 1.0 < 0.5 < 5' 0

. < 1.0 < 0.5 12/18 *2/22 < 5.0 3.6

1.0 < 0.5 < 5.0 < 1.0 < 0.5 12/25-12/29 10.6 i 2.8 12.9 0.9 6.4 0.5 < 5.0 < 1.0 < 0.5 1979 1/1-1/5 < 5.0 4.1

0.7 1.7

0.4 < 5.0 < 1.0 < 0.5 1/8-1/12 < 5.0 < 1.0 1.0 0.4 < 5.0 < 1.0 < 0.5 1/15-1/19 9.4

2.2 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 1/22-1/26 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 1/29-2/2 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 2/5-2/9 7.6

1.8 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 2/12-2/16 10.5

2.8 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 2/19-2/23 6.7 2.7 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 2/26-3/2 < 5.0 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 3/5-3/9 5.9 i 2.0 < 1.0 < 0. 5 < 5.0 < 1.0 < 0.5 3/12-3/16 12.9 i 3.2 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 3/19-3/23 9.6 2.6 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5 3/26-3/30 8.9 t 2.1 < 1.0 < 0.5 < 5.0 < 1.0 < 0.5

[j ' 3 50

4 Table 3.1 lElk Specific Activity (pci/1

1 0) 90g , 131 Date 7 10/78 3.28 i 0.43 < 2.0 11/78 3.69

0.59 < 2.0 12/78 10.45

0.62 < 2.0 1/79 3.93

0.48 < 2.0 2/79 2.43

0.51 < 2.0 3/79 2.93

0.37 < 2.0 Table 4.1 Surfaco Water Specific Activity (pCi/1

1 o )

Og 90 Gross Alpha Gross Beta Date Location

Cs Sr 1978 Oct ON < 0.1 < 2.0 0.22 0.02 0.23 i 0.07 2.86 0.35 0FF < 0.1 < 2.0 0.23

0.02 0.20 0.07 4.44

0.A2 Nov ON < 0.1 < 2.0 0.05 0.02 0.28

0.00 4.69

0.41 0FF < 0.1 < 2.0 0.09

0.02 0.16 0.06 5.38

0.44 Dec ON < 0.1 < 2.0 0.37

0.03 0.44 6 0.09 6.21

0.49 CFF < 0.1 < 2.0 0.38 i 0.03 0.23

0.07 5.19 i 0.44 1979 Jan ON < 0.1 < 2.0 0.36 0.03 0.36 0.09 4.03 0.38 0FF 0.25 0.71 39.59142.05 0.33 i 0.03 0.30

0.08 8.33

0.59 Feb ON 0.33 Cell 18.29i41.95 0.31

0.03 1.02 i 0.14 7.95

0.57 0FF 0.33

0.71 < 2.0 0.82

0.06 0.43 i 0.09 7.73

0.56 Mar ON < 0.1 < 2.0 C.':0 0.03 0FF < 0.1 < 2.0 0.20

0.03

ON . Denoteo Rocky Branch Crock on it ett.cre UCSU Campuc 0FF . Denotes Rocky Branch Crock no it lenvec NCSU Crepus Table 5.1 Soil Specific Act.ivity (pC1/gr i 1 0 )

2?8 '*6 137 40 Location

Greer ce Orarn 3 Th ~' Ra Cs K North 1.1160.?.3 10.32il.73 0.3720.35 0.91*0.36 4.4Sio.36 < 0.4 South 1.07*0.36 0.75 1.46 0.45io.41 0.9400.41 4.05*0.38 < 0.4 Eaot 1.3 3i0 . 17 10.36it,43 1.32i0.61 1.23 0.47 2.99=0.36 < 0.4 Ucot 2.30*0.7'. 19.93i2.31 1.67S0.39 1.25io.46 3.20i0.36 42.09 17.96 W (4.5') 1. 62io . 3'1 12.V' 2.07 0.G3P.32 1.11i0.21 0.19=0.15 19.73i9.63 OBG(4.5') 2.27 0.43 26.~5+2.35 2.30 0.66 0.81.20.35 0.26io.22 40.09*13.89 NBG(4.5') 4.83do.79 18,01*2.37 0.925).32 4.4010.45 0.39*0.25 19.49i15.66

Location . Denotes directica fres reactor Burial ground ccaples cre in nent proximity to fence NBG denotec Neu Burici Ground OEG denotes Old Burial Cround (Uot precently in ttun) 4.5' denotco depth of semple, othern are et curice.c r,'. 7 G ~/

L O) ?'I

___ .~ _ . . .

Table 6.1 Vegetation Specific Activity (pCi/gm

i c) 5 40g Sempic Gross Alpha Gross Beta Cs Corn < 0.01 3.20

0.18 0.051

0.044 7.07

2.78 Soy Beans 0.15 i O.03 14.81 0.79 0.109 i 0.028 53.76

3.20 Reactor Pine 0.05 0.03 2.87 0.23 0.012 i O.057 4.85

3.71 South Pine 0.09

0.03 2.49 0.22 0.083

0.061 9.03 i 3.76 Table 7.1 Tank and Sewage Specific Activity (pCi/1 i 1 o )

Sampic Gross Alpha Gross Beta ' Sr WT #2 Oct < 0.5 3267

175 WT #3 Oct < 0.5 3376

180 WT #1 Nov < 0.5 613 42 UT #3 No'- < 0.5 371

30 -

UT #1 Dec < 0.5 211

22 WT #3 Dec < 0.5 349

29 UT #1 Jan < 0.5 523 i 37 Int #3 Jan < 0.5 497 i 36 UT #1 Feb < 0.5 704 47 UT #3 Feb < 0.5 330 i 28 UT #2 Mar < 0.5 068 54 WT #3 Mar < 0.5 1191 71 Oct Scuoge 0.20 i 0.14 ?l.55 1.0? 1.53 = 0.41 Dec Scunge < 0.1 9 56 ".95 1.33 0.41 Feb Seunge < 0.1 17.44 i- 1 31 0.56

0.22 n T 7rO U '. u .s U

--.-.- ~ _ - - . . . - - . . . . - --

6 Table 3.1 Themoluminescent Dosimeter (TLD) Locations Designation Locatica Broughton 410 f t. southvent of cad 55 ft. below top of Reactor Stack DCL Roof of David Clark Laboratories Library 629 f t. northuest of and 36 ft. above top of Reactor Stack Riddick 325 ft. coutheast of and 46 ft, below top of Reactor Stack Withers 270 f t northeast of and 19 f t. belov top of Reactor Scack Control Room 214 David Clark Laba R-3 Entrance to NCSUR-3 Reactor Bay fror Control Room PULSTAR PULSTAR Rdactor Bay, West Wall Er,uipment Room PULSTAR Equipment Rocci East of PULSTAR Bay Control Room PULSTAR Control Room Pool ' Over PULSTAR Reactor Pool Stack Top of PULSIAR Reacect Stack Tabic 8.2 Thermoluminescent Desimeter Readings (Averago mR/wk based on Co.60 Standard)

Area Monitors

10/78 11/78 12/78 1/79 2/79 3/79 Broughton L 3.2 3.8 3.7 X X 3.7 Broughton C 0.7 2.8 2.0 2.0 1.8 1.8 DCL L 2.3 3.1 2.4 X X 2.8 DCL C < 0.1 2.2 1.5 1.3 1.0 0.7 Library L 3.2 3.8 3.6 X X 3.6 Library C 0.5 2.9 2.0 1.9 1.8 1.8 Riddick L 3.4 3.8 3.9 X X 4.2 Riddick C 1.0 3.0 2.2 2.0 2.0 2.6 Withers L 3.0 3.0 3.0 X X 3.0 Uithers C 0.4 2.1 1.4 1.6 1.3 1.8 Control L 3.0 3.0 1.3 X X 2.8 Control C 0.3 2.3 2.0 1.4 1.8 1.4 Reactor Monitors n-3 L 6.0 5.9 6.4 X X 6.0 R-3 C 6.3 3.6 3.4 3.1 2.9 3.1 FULSTAR L 97.4 87.0 14.5 X X 53.8 PULSIAR C 13.3 12.2 8.3 8.8 11.4 26.8 Equioment Room L 30.0 19.9 27.9 X X 32.3 Equipment Room C 23.8 17.7 18.3 21.4 21.3 24.2 Control Room L 10.2 9.6 6.0 X X 3.6 Control Room C 3.0 4.0 3.5 3.4 3.8 3.7 Pool L 50.8 47.9 40.0 X X 48.9 Pool C 32.8 30.1 23.8 30.2 28.6 21.2 Secek L 2.8 3.8 4.0 X X 4.9 Stack C 0.2 2.5 1.6 1.7 1.5 2.2

L - Denates Locally Evaluated LiF Dosimeters C - Denotes CaSO 4 : Dy Dosimetero Contracted to Toledync Isotopes for analysis X - TLD Reader used for local evaluations was not operationni and in repair status for January and February 1979 0 '; /Gt O_) .> J}

ML19254A785

Text

Reference:

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